U.S. patent application number 11/502329 was filed with the patent office on 2010-10-28 for storage-transport system and method for storing and transporting radioactive waste.
This patent application is currently assigned to Framatome ANP GmbH. Invention is credited to Michael Freiman, Viktor Gliha, Werner Werschnik.
Application Number | 20100270482 11/502329 |
Document ID | / |
Family ID | 34801866 |
Filed Date | 2010-10-28 |
United States Patent
Application |
20100270482 |
Kind Code |
A1 |
Werschnik; Werner ; et
al. |
October 28, 2010 |
Storage-transport system and method for storing and transporting
radioactive waste
Abstract
A storage-transport system includes a storage container and a
transport container for respectively storing and transporting weak
to intermediate level active nuclear waste. The storage-transport
system has different containers for the functions of storage and
transport, namely the storage container and the transport
container. The storage container only meets the requirements for
temporary storage which are less strict than the requirements for
the transport container, thereby allowing for a simple and
therefore less expensive construction of the storage container. A
method for storing and for transporting radioactive waste is also
provided.
Inventors: |
Werschnik; Werner;
(Russelsheim, DE) ; Freiman; Michael; (Konigstein,
DE) ; Gliha; Viktor; (Hanau, DE) |
Correspondence
Address: |
LERNER GREENBERG STEMER LLP
P O BOX 2480
HOLLYWOOD
FL
33022-2480
US
|
Assignee: |
Framatome ANP GmbH
|
Family ID: |
34801866 |
Appl. No.: |
11/502329 |
Filed: |
August 10, 2006 |
Related U.S. Patent Documents
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Application
Number |
Filing Date |
Patent Number |
|
|
PCT/EP05/00786 |
Jan 27, 2005 |
|
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11502329 |
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Current U.S.
Class: |
250/507.1 ;
250/506.1 |
Current CPC
Class: |
G21F 5/00 20130101; G21F
5/14 20130101; G21F 5/005 20130101 |
Class at
Publication: |
250/507.1 ;
250/506.1 |
International
Class: |
G21F 5/005 20060101
G21F005/005; G21F 5/14 20060101 G21F005/14; G21F 5/12 20060101
G21F005/12 |
Foreign Application Data
Date |
Code |
Application Number |
Feb 10, 2004 |
DE |
10 2004 006 620.5 |
Claims
1. A storage-transport system for storing and for transporting
radioactive waste, the transport system comprising: a storage
container for accommodating the radioactive waste; and a cover
loosely placed on said storage container to close said storage
container; said storage container meeting relatively less stringent
requirements regarding shielding capacity against radioactive
radiation for storage in a storage facility, but not meeting
relatively more stringent requirements for transportation outside
the storage facility; and said storage container being configured
for placement in a transport container meeting the relatively more
stringent transportation requirements for transportation outside
the storage facility.
2. The storage-transport system according to claim 1, wherein said
storage facility is an interim storage facility.
3. The storage-transport system according to claim 2, wherein said
storage container is constructed merely for complying with a
relatively high maximum admissible radiation-dose output in the
interim storage facility, but not for complying with a relatively
low maximum admissible radiation-dose output outside the interim
storage facility.
4. The storage-transport system according to claim 1, wherein said
storage container does not meet predetermined transportation
requirements for mechanical stability.
5. The storage-transport system according to claim 1, wherein said
storage container is configured for accommodating a plurality of
receptacles with radioactive waste.
6. The storage-transport system according to claim 5, wherein said
receptacles are drums.
7. The storage-transport system according to claim 1, wherein said
storage container is configured for accommodating solid radioactive
waste.
8. (canceled)
9. The storage-transport system according to claim 1, wherein said
storage container is stackable with other storage containers.
10. The storage-transport system according to claim 1, wherein said
storage container has side walls and a base formed of a material
selected from the group consisting of concrete and steel.
11. The storage-transport system according to claim 1, which
further comprises a transport container for accommodating said
storage container, said transport container being constructed to
meet the relatively more stringent transportation requirements.
12. The storage-transport system according to claim 11, wherein
said transport container is constructed for repeated transportation
of storage containers.
13. The storage-transport system according to claim 12, wherein
said transport container has a container cover to be closed
repeatedly.
14. The storage-transport system according to claim 13, wherein
said container cover is motor-actuated.
15. The storage-transport system according to claim 11, wherein
said storage container has external dimensions, and said transport
container has internal dimensions adapted to said external
dimensions of said storage container.
16. The storage-transport system according to claim 15, wherein
said transport container has side walls and guide profiles disposed
on said side walls for introduction and retention of said storage
container.
17. The storage-transport system according to claim 11, wherein
said transport container is a steel container.
18. A method for storing and for transporting radioactive waste,
the method comprising the following steps: providing a storage
container meeting relatively less stringent requirements regarding
shielding capacity against radioactive radiation for storage in a
storage facility, but not meeting relatively more stringent
requirements for transportation outside the storage facility;
introducing the radioactive waste into the storage container;
closing the storage container by loosely placing a cover on the
storage container; positioning the storage container in the storage
facility; and placing the storage container in a transport
container meeting the relatively more stringent transportation
requirements for transportation outside the storage facility.
19. The method according to claim 18, wherein the storage facility
is an interim storage facility.
20-21. (canceled)
Description
CROSS-REFERENCE TO RELATED APPLICATIONS
[0001] This is a continuing application, under 35 U.S.C. .sctn.120,
of copending International Application No. PCT/EP2005/000786, filed
Jan. 27, 2005, which designated the United States; this application
also claims the priority, under 35 U.S.C. .sctn.119, of German
Patent Application DE 10 2004 006 620.5, filed Feb. 10, 2004; the
prior applications are herewith incorporated by reference in their
entirety.
BACKGROUND OF THE INVENTION
Field of the Invention
[0002] The invention relates to a storage-transport system and to a
method for storing and for transporting radioactive waste.
[0003] Following cost-effective use of radioactive materials, the
latter have to be disposed of in a suitable manner due to their
residual radiation and long half-lives. Considerable quantities of
radioactive waste are produced, in particular in the case of energy
being generated through the use of nuclear power. In addition to
spent fuel elements, those quantities of radioactive waste also
include low-level and medium-level radioactive waste, for example
contaminated operating equipment. Liquid radioactive waste is often
cast, in a cementation installation, into a solid mass which is
introduced, for example, into drums.
[0004] Safe storage of the waste has to be ensured due to the very
long half-lives. At present, in Germany, the radioactive waste is
stored in interim storage facilities over a period of a number of
years until being transported, at the end of that period, into a
yet-to-be-determined final storage facility.
[0005] It is thus necessary for those containers, into which the
radioactive waste has been introduced, to meet requirements with
respect to storage both in the interim storage facility and in the
final storage facility, as well as requirements with respect to
necessary transportation, for example between the interim storage
facility and the final storage facility. As a result, the
containers have to meet very stringent requirements overall both
with respect to providing shielding for radiation of the
radioactive waste located in the container and with respect to a
sufficiently high level of transportation safety, for example by
way of sufficiently high mechanical stability, in order to reliably
avoid the leakage of radioactivity in the event of an accident
during transportation. Furthermore, the containers have to be
constructed so as to be capable of transportation and handling.
Those requirements render current transporting and storage
containers highly complex and correspondingly expensive.
SUMMARY OF THE INVENTION
[0006] It is accordingly an object of the invention to provide a
storage-transport system and a method for storing and for
transporting radioactive waste, which overcome the
hereinafore-mentioned disadvantages of the heretofore-known devices
and methods of this general type and which allow simplified and
more cost-effective storage and simplified and more cost-effective
transportation, in particular of low-level and medium-level
radioactive waste.
[0007] With the foregoing and other objects in view there is
provided, in accordance with the invention, a storage-transport
system for storing and for transporting radioactive waste. The
transport system comprises a storage container for accommodating
the radioactive waste. The storage container meets relatively less
stringent requirements regarding shielding capacity against
radioactive radiation for storage in a storage facility, in
particular an interim storage facility, but does not meet
relatively more stringent requirements for transportation outside
the storage facility. The storage container is configured for
placement in a transport container meeting the relatively more
stringent transportation requirements for transportation outside
the storage facility.
[0008] This configuration is based on the concept of taking into
account the different requirements with respect to storage and
transportation of the storage and transportation functions of a
container for radioactive waste being separated and divided between
two containers constructed to meet different requirements. To be
precise, a specific storage container which, for transportation, is
transported into a suitable transport container is provided. Due to
the more low-level requirements with respect to storage in the
interim storage facility, this measure allows the storage container
to have a considerably more straightforward and, in particular,
more cost-effective construction than is possible for the current
conventional containers, which are constructed both for storage and
for transportation purposes.
[0009] Separating the storage and transportation functions, in
addition, makes it possible to select different storage systems for
the final storage facility. Since the interim storage facilities
are constructed, for example, for a half-life of 30 years, it is
thus possible to take into account technical developments and
findings for final storage purposes.
[0010] In particular, the containers have to meet requirements, on
one hand, with respect to providing shielding for the radioactive
radiation and, on the other hand, with respect to mechanical
stability. Both requirements are usually considerably less
stringent in the interim storage facility since, for example, in
comparison with transportation, there is no risk of an accident
during storage (mechanical stability). It is also the case that the
interim storage facility itself, which is in the form of a
dedicated part of a building, for example directly on the grounds
of a nuclear plant, provides shielding for the radioactive
radiation, whereas during transportation, the container comes into
direct contact with the environment and thus has to provide better
shielding than in the interim storage facility. The containers in
this case have to be constructed in such a way that a maximum
admissible radiation-dose output is not exceeded.
[0011] In accordance with another feature of the invention, the
storage container is constructed merely for complying with a
relatively high maximum admissible radiation-dose output in the
interim storage facility, but not for complying with a relatively
low maximum admissible radiation-dose output outside the interim
storage facility. It is only by placing the storage container in
the transport container that the radiation-dose output also drops
below the relatively low maximum admissible value outside the
interim storage facility.
[0012] In accordance with a further feature of the invention, the
storage container is provided for accommodating a plurality of
receptacles with radioactive waste, in particular for accommodating
drums. This simplifies the handling of the receptacles and allows
the latter to be handled together. It is also possible, if
required, to provide for additional measures for shielding purposes
and for increasing the mechanical stability. Thus, for example, for
final storage purposes, the receptacles stored in the storage
container are preferably cast in place in the storage container. In
an alternatively advantageous configuration, without reverting to
the use of receptacles, the storage container is provided for
accommodating solid radioactive waste.
[0013] In accordance with an added feature of the invention, in
order to ensure accessibility to the individual receptacles, in
particular drums, in the storage container, the storage container
is closed merely by a loosely or releasably disposed cover. This
measure thus makes it possible, at any time, to remove the cover
and, for example, automatically inspect and monitor the stored
drums. Furthermore, it is also possible to handle the individual
receptacles. In particular, the configuration with the loose cover
makes it possible, for final storage purposes, for the individual
receptacles to be stored in accordance with the most recent
technological findings.
[0014] In accordance with an additional feature of the invention,
in order to provide storage in the interim storage facility which
is as space-saving and stable as possible, the storage container
preferably has a stackable construction. For this purpose, the
container has, for example, a rectangular cross section and, on its
underside, feet and, on the top side, mounts or guides for the feet
of a further storage container, as is provided in conventional
stacking containers.
[0015] In accordance with yet another feature of the invention, the
storage container is constructed in such a way that its side walls
and its base are formed of a concrete structure or of steel. The
concrete structure may be provided with corresponding
reinforcement. The concrete structure makes it possible,
straightforwardly and cost-effectively, to achieve both good
shielding and sufficient mechanical stability for storage purposes.
In this case, however, the wall thicknesses are smaller than in the
case of a container constructed for transportation purposes.
[0016] In accordance with yet a further feature of the invention,
in order to keep the costs low, the transport container is
constructed for repeated transportation of storage containers. Only
a small number of transport containers is required by virtue of it
being possible to reuse the transport container. Correspondingly,
it is possible for the transport container to be very complex and
constructed to meet highly stringent safety requirements without
this having a marked influence on the costs for the
storage-transport system overall. It is expedient, for repeated
loading and unloading of the transport container, for the latter to
be configured with a container cover which, in particular, can be
motor-actuated and closed repeatedly.
[0017] In accordance with yet an added feature of the invention, in
order for the storage container to fit as closely, and thus
reliably, as possible in the transport container, the internal
dimensions of the transport container are adapted to the external
dimensions of the storage container. In order for the storage
container to be straightforwardly introduced and securely retained,
guides which are constructed, in particular, in the manner of
profiles or strips are preferably provided, in addition, on the
walls of the transport container. These guides allow the storage
container to be retained in the transport container, as far as
possible, in a play-free manner. The guides preferably have
introduction slopes for easy introduction.
[0018] In accordance with yet an additional feature of the
invention, the transport container is constructed as a steel
container from a suitable steel with a high shielding capacity and
high mechanical stability.
[0019] With the objects of the invention in view, there is also
provided a method for storing and for transporting radioactive
waste. The method comprises providing a storage container meeting
relatively less stringent requirements regarding shielding capacity
against radioactive radiation for storage in a storage facility, in
particular an interim storage facility, but not meeting relatively
more stringent requirements for transportation outside the storage
facility. The radioactive waste is introduced into the storage
container. The storage container is positioned in the storage
facility. The storage container is placed in a transport container
meeting the relatively more stringent transportation requirements
for transportation outside the storage facility.
[0020] The preferred configurations and advantages which have been
cited with respect to the storage-transport system can also be
applied analogously to the method.
[0021] Other features which are considered as characteristic for
the invention are set forth in the appended claims.
[0022] Although the invention is illustrated and described herein
as embodied in a storage-transport system and a method for storing
and for transporting radioactive waste, it is nevertheless not
intended to be limited to the details shown, since various
modifications and structural changes may be made therein without
departing from the spirit of the invention and within the scope and
range of equivalents of the claims.
[0023] The construction and method of operation of the invention,
however, together with additional objects and advantages thereof
will be best understood from the following description of specific
embodiments when read in connection with the accompanying
drawings.
BRIEF DESCRIPTION OF THE DRAWINGS
[0024] FIG. 1 is a diagrammatic, partly-sectional, side-elevational
view of a storage container according to the invention with a cover
provided for loose placement in position;
[0025] FIG. 2 is a further partly-sectional, side-elevational view
of the storage container according to FIG. 1;
[0026] FIG. 3 is a plan view of the storage container according to
FIGS. 1 and 2, indicating section lines I-I of FIG. 1 and II-II of
FIG. 2;
[0027] FIG. 4 is a perspective view of a transport container;
[0028] FIG. 5 is a side-elevational view of the transport container
according to FIG. 4, with a diagrammatically illustrated driver's
cab of a truck; and
[0029] FIG. 6 is a block diagram demonstrating disposal of
radioactive waste.
DESCRIPTION OF THE PREFERRED EMBODIMENTS
[0030] Referring now to the figures of the drawings in detail and
first, particularly, to FIGS. 1-3 thereof, there is seen a storage
container 2 which is constructed in such a way that its side walls
4, together with its base 6, are formed of a single-piece concrete
structure. A cover 8, which is preferably likewise made of
concrete, is provided with a gripping device 9 for the purpose of
closing the storage container 2. The cover 8 is merely placed
loosely in position on the side walls 4 for the purpose of closing
the storage container 2. The storage container 2 has a rectangular
outline and a stackable construction. For this purpose, feet 10 are
disposed at four corner points on the underside of the base 6. The
side walls 4 each carry mounts or guides 12 on their top end side
at the four corners. The feet 10 of a further storage container 2
are introduced into these mounts or guides during stacking of this
further storage container.
[0031] In the exemplary embodiment, the storage container 2 is
provided for accommodating a total of 8 radioactive receptacles in
the form of drums 14. In order to prevent the drums 14 from
slipping, the base 6 has a profile construction on its top side and
has, in particular, rhomboidal elevations, resulting in the
formation of a total of 8 separate accommodating spaces for the
drums 14, as is seen in FIG. 3.
[0032] A transport container 20, which can be seen in FIGS. 4 and 5
in particular, is adapted specifically for transportation within
the grounds of a power station. In the exemplary embodiment, it is
constructed as a steel container and can be closed by a double-wing
container cover 22. Two motors 26 are provided on an outer end side
of a side wall 24 of the container for the purpose of reversible
opening and closing. These motors 26 are each connected, through an
extensible linkage 28, to a respective wing of the container cover
22 in order for the wing to be reversibly opened and closed.
[0033] Locking and securing devices 30 for the container cover 22
are also disposed on the side wall 24 of the container.
[0034] Guide profiles 32 in the interior of the container are
fastened on the side walls 24 of the container. These guide
profiles 32 have an introduction slope 34 on their top end side.
The internal dimensions of the transport container 20 are such that
the storage container 2, which has been 1) described in relation to
FIGS. 1-3, fits as closely as possible between the guide profiles
32. The introduction slope 34 makes it easier for the storage
container 2 to be introduced. This introduction slope, at the same
time, also provides for automatic alignment and centering of the
storage container 2.
[0035] The transport container 20 is provided for transportation
through the use of a truck 36, of which the driver's cab is
illustrated diagrammatically in FIG. 5. The transport container 20
in this case is connected to the truck by suitable screw
connections or other types of releasable connections or else in a
non-releasable manner by welding.
[0036] The storage container 2 and the transport container 20 form
part of a common concept for storing and for transporting low-level
and medium-level radioactive waste. The important factor in this
concept is to be seen in the fact that the storage and
transportation functions are divided between two different
container combinations. Thus, on one hand, the storage container 2
is constructed merely for storage, in particular in a
non-illustrated interim storage facility, whereas the
transportation function is performed by the transport container 20
combined with the storage container 2 introduced therein. Different
regulations and requirements apply for the storage of radioactive
waste in an interim storage facility and for the transportation of
radioactive waste, not in the least because of legal requirements.
Since a building which forms the interim storage facility also
performs a shielding function with respect to the surroundings and,
in addition, there is no transportation-related accident risk, the
requirements with respect to storage in the interim storage
facility are considerably less stringent than the requirements
which have to be met by the transport container. Accordingly, the
storage container 2 is constructed merely to meet the requirements
which apply to the interim storage facility. In comparison with a
transport container constructed for transportation purposes, this
is manifested by a lower shielding capacity and, in addition, also
by a lower level of sealing and mechanical stability. The storage
container 2 is thus configured in such a way that, when a
radioactive waste with a certain initial level of radioactivity is
stored therein, the radiation-dose output drops below the maximum
admissible value which applies to the interior of the interim
storage facility, but does not drop below the lower, and thus more
critical, maximum admissible value outside the interim storage
facility.
[0037] The shielding capacity of the storage container 2 is
determined substantially by the material selected for the side
walls 4, the base 6 and the cover 8 and by the density of the
material and the wall thickness. The configuration of the storage
container 2 in order to meet the more low-level requirements within
the interim storage facility is manifested, for example, in such a
way that, in each case in comparison with a container which also
has to meet transportation requirements:
a) if use is made of the same material, the wall thickness is
smaller, b) if use is made of the same material, the latter may
have a lower density, and c) use can be made, overall, of a more
cost-effective material with a lower shielding capacity and/or
lower mechanical stability.
[0038] In particular, this gives rise to considerable cost-saving
opportunities in comparison with a container which is constructed
both as a storage and as a transport container.
[0039] In the exemplary embodiment of FIGS. 1-3, the storage
container 2 is constructed as a concrete container. It is also
possible for the storage container 2 to be formed of some other
material or material mix and to be constructed, for example, as a
steel container.
[0040] The more stringent requirements with respect to
transportation are manifested, for example, in the above-mentioned
lower maximum admissible radiation-dose output and in the more
stringent requirements which have to be met by the mechanical
stability in order to take into account the greater risk of an
accident during transportation. The more stringent transportation
requirements are met by the transport container 20 combined with
the storage container 2 inserted therein. It is also possible for
the transport container 20 to already be constructed in such a way
that it alone meets the transportation requirements so that, in
principle, it would also be possible for receptacles containing the
radioactive waste to be introduced loosely into the transport
container 20.
[0041] The transport container 20 basically serves for
transportation purposes within the power-station grounds. In
contrast, in order to transport the storage container 2 outside an
interim storage facility 40, for example for transporting the
storage container 2 from an installation for conditioning the
radioactive waste, such as a cementation installation 42, into the
interim storage facility 40, as well as for transporting the
storage container from the interim storage facility 40 into a final
storage facility 44, as is diagrammatically illustrated in
simplified form in FIG. 6, or for other transporting trips on
public roads, a transport container which meets the requirements
stipulated by IAEA is provided. The conditioning installation 42 is
illustrated in this case as part of a nuclear plant 46. The interim
storage facility 40 may be a specific building on the grounds of
the nuclear plant.
[0042] During operation of the nuclear plant 46, in particular for
generating energy (nuclear power station), both solid and liquid
low-level and medium-level radioactive waste is produced and has to
be disposed of in a suitable manner. In particular in the case of
liquid waste, provision is often made for such waste to be mixed
with a suitable cement mass in the cementation installation 42 and
introduced into the above-mentioned drums 14, in which the mass
then solidifies. These drums 14 which are filled in the cementation
installation 42 are inserted into the storage container 2, and the
storage container 2 is then inserted into the transport container
20 and transported into the interim storage facility 40, where the
storage container 2 is lifted out of the transport container 20
again and positioned in a storage location envisaged therefor.
Respectively suitable cranes or lifting apparatuses are provided
for handling the drums 14 and the storage container 2, in the
process of which they grip the drums 14 and/or the storage
container 2 at suitable locations.
[0043] The cover 8 of the storage container 2 need only be placed
in position loosely, not in the least because of the relatively
low-level requirements in the interim storage facility 40. This
provides the advantage that, during the storage period in the
interim storage facility, it is possible for the cover 8 to be
easily removed and for the drums 14 stored therein to be inspected
and monitored and exchanged, if required, for example in the event
of leakage. The cover 8 has the gripping device 9 on its top side
for the purpose of handling the same.
[0044] A further significant advantage of the cover 8 only being
loosely or releasably placed in position is that there is no need
to decide on the method of conditioning the radioactive waste at
the interim storage stage. Rather, the option for the definitive
conditioning method remains open until the radioactive waste is
moved into the final storage facility 44. Since the interim storage
facility 40 is constructed, for example, for storing waste over a
period of 30 years, that is to say a number of decades can elapse
before the waste is transported into the final storage facility 44,
this measure makes it possible to take into account future
technological developments or findings for definitive conditioning.
This is particularly advantageous since the storage container 2 can
be used not just for accommodating drums 14 but also for
accommodating loose radioactive waste. A comparatively
straightforward conditioning method for the final storage facility
44 is that of using a suitable cement mass to fill the storage
container 2, with the drums 14 stored therein.
* * * * *